Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Neutronic Analysis Of Horizontal Compact High Temperature Gas Cooled Reactor
Download Neutronic Analysis Of Horizontal Compact High Temperature Gas Cooled Reactor full books in PDF, epub, and Kindle. Read online Neutronic Analysis Of Horizontal Compact High Temperature Gas Cooled Reactor ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Neutronic Analysis of Horizontal-compact High Temperature Gas-cooled Reactor by : Kristina (Nuclear engineering researcher)
Download or read book Neutronic Analysis of Horizontal-compact High Temperature Gas-cooled Reactor written by Kristina (Nuclear engineering researcher) and published by . This book was released on 2023 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: To address the significant cost challenges associated with advanced reactors, a 150MWt horizontal compact high temperature gas-cooled reactor (HC-HTGR) has been proposed. The HC-HTGR has potential to reduce the capital cost of a traditional vertical oriented HTGR by 20% through reduction in reactor building volume. This benefit comes with a trade-off in control system design that requires the usage of control drums due to sagging thin rods in a horizontal layout. Commonly utilized in microreactors, a thorough investigation of control drums must be conducted in reactors with power >100MWt. Parametric studies using OpenMC were carried out to ensure its feasibility. With a uniform enriched core, 12 rotating control drums with an outer radius of 23.4407cm, 0.5cm thickness of 90% enriched B[subscript 4]C, and 0.3cm incoloy cross supports, achieved the highest shutdown margin (SDM) of 3.23%. A sensitivity study on fuel enrichment yielded a SDM of 6.29%, that satisfied the HTGRs design requirement. 2D radial and axial power peaking factor (PPF) with the new enrichment pattern was found at 1.847 and 1.344, respectively. Homogenization using ring reactivity equivalent physical transformation (RRPT) method was developed to reduce the complexity of the core and showed a good performance with a 4pcm difference in steady-state calculation. Depletion analysis was modeled to ensure the reliability of the new fuel enrichment pattern. The first cycle core sustained criticality for 2.37 years with an average enrichment of 15.5% which meets the design target goal of 2 years cycle length. Overall, the neutronics assessment of HC-HTGR core met the initial safety and design requirements.
Book Synopsis Maritime Gas-cooled Reactor Program by : A. J. Goodjohn
Download or read book Maritime Gas-cooled Reactor Program written by A. J. Goodjohn and published by . This book was released on 1961 with total page 94 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Beginning-of-life Neutronic Analysis of a 3000-MW(t) HTGR. by :
Download or read book Beginning-of-life Neutronic Analysis of a 3000-MW(t) HTGR. written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The results of a study of safety-related neutronic characteristics for the beginning-of-life core of a 3000-MW(t) High-Temperature Gas-Cooled Reactor are presented. Emphasis was placed on the temperature-dependent reactivity effects of fuel, moderator, control poisons, and fission products. Other neutronic characteristics studied were gross and local power distributions, neutron kinetics parameters, control rod and other material worths and worth distributions, and the reactivity worth of a selected hypothetical perturbation in the core configuration. The study was performed for the most part using discrete-ordinates transport theory codes and neutron cross sections that were interpolated from a four-parameter nine-group library supplied by the HTGR vendor. A few comparison calculations were also performed using nine-group data generated with an independent cross-section processing code system. Results from the study generally agree well with results reported by the HTGR vendor. (auth).
Book Synopsis Gas Cooled Nuclear Reactor Study by : A. S. Thompson
Download or read book Gas Cooled Nuclear Reactor Study written by A. S. Thompson and published by . This book was released on 1956 with total page 130 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Advances in High Temperature Gas Cooled Reactor Fuel Technology by : International Atomic Energy Agency
Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
Book Synopsis Thermal and Flow Design of Helium-cooled Reactors by : Gilbert Melese
Download or read book Thermal and Flow Design of Helium-cooled Reactors written by Gilbert Melese and published by . This book was released on 1984 with total page 444 pages. Available in PDF, EPUB and Kindle. Book excerpt: This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.
Book Synopsis Neutronic and Thermal-hydraulic Coupling Study on High Temperature Gas-cooled Reactor by : Cheng-Kai Tai
Download or read book Neutronic and Thermal-hydraulic Coupling Study on High Temperature Gas-cooled Reactor written by Cheng-Kai Tai and published by . This book was released on 2017 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen
Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.
Book Synopsis 40-MW(E) Prototype High-temperature Gas-cooled Reactor Research and Development Program by :
Download or read book 40-MW(E) Prototype High-temperature Gas-cooled Reactor Research and Development Program written by and published by . This book was released on 1961 with total page 258 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Modular High-temperature Gas-cooled Reactor Short-term Thermal Response to Flow and Reactivity Transients by :
Download or read book Modular High-temperature Gas-cooled Reactor Short-term Thermal Response to Flow and Reactivity Transients written by and published by . This book was released on 1993 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The research reported here has been conducted at the Oak Ridge National Laboratory for the Nuclear Regulatory Commission's Division of Regulatory Applications of the Office of Nuclear Regulatory Research. The short-term thermal response of the Modular High-Temperature Gas-Cooled Reactor (MHTGR) is analyzed for a range of flow and reactivity transients. These transients include loss of forced circulation without scram, spurious withdrawal of a control rod group, moisture ingress, control rod and control rod group ejections, and a rapid core cooling event. For each event analyzed, an event description, a discussion of the analysis approach and assumptions, and results are presented. When possible, results of these analyses are compared with those presented by the designers in the MHTGR Preliminary Safety Information Document and in the MHTGR Probabilistic Risk Assessment. The importance of inherent safety features is illustrated, and conclusions are presented regarding the safety performance of the MHTGR. Recommendations are made for a more in-depth examination of MHTGR response for some of the analyzed transients. The coupled heat transfer-neutron kinetics model is described in detail in Appendix A.
Book Synopsis Gas-cooled Reactors Today: Papers, discussion, closing address, corrigenda by :
Download or read book Gas-cooled Reactors Today: Papers, discussion, closing address, corrigenda written by and published by . This book was released on 1982 with total page 338 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Gas-cooled Reactors Today: Performance and safety technology, status of gas-cooled reactors by :
Download or read book Gas-cooled Reactors Today: Performance and safety technology, status of gas-cooled reactors written by and published by . This book was released on 1982 with total page 298 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Maritime Gas-cooled Reactor Program by : A. J. Goodjohn
Download or read book Maritime Gas-cooled Reactor Program written by A. J. Goodjohn and published by . This book was released on 1961 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Multiphase Flow and Heat Transfer in Pebble Bed Reactor Core by : Shengyao Jiang
Download or read book Multiphase Flow and Heat Transfer in Pebble Bed Reactor Core written by Shengyao Jiang and published by Springer Nature. This book was released on 2020-11-19 with total page 510 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book introduces readers to gas flows and heat transfer in pebble bed reactor cores. It addresses fundamental issues regarding experimental and modeling methods for complex multiphase systems, as well as relevant applications and recent research advances. The numerical methods and experimental measurements/techniques used to solve pebble flows, as well as the content on radiation modeling for high-temperature pebble beds, will be of particular interest. This book is intended for a broad readership, including researchers and practitioners, and is sure to become a key reference resource for students and professionals alike.
Book Synopsis A Parametric Study of the Gas-cooled Reactor Concept by : Hanford Atomic Products Operation
Download or read book A Parametric Study of the Gas-cooled Reactor Concept written by Hanford Atomic Products Operation and published by . This book was released on 1958 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Evaluation of High-temperature Gas-cooled Reactors by : Oak Ridge National Laboratory
Download or read book An Evaluation of High-temperature Gas-cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1969 with total page 236 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Final Summary Report of the Gas-cooled Reactor Experiment-I by : R. H. Chesworth
Download or read book Final Summary Report of the Gas-cooled Reactor Experiment-I written by R. H. Chesworth and published by . This book was released on 1963 with total page 208 pages. Available in PDF, EPUB and Kindle. Book excerpt:
